ML19250G266
| ML19250G266 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/31/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18023A006 | List: |
| References | |
| NUDOCS 8105080086 | |
| Download: ML19250G266 (9) | |
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T0pICAL REPORT EVALUATION
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Report Number:
WCAP 8252, Rev. 1 Report
Title:
Documentation of Selected Nestinghouse Structural Analysis
[:g Computer Codes Report Dat~
tiay 1977 Originating 'rganiz.ation: Westinchouse Electric Corporation Reviewed By: tiechanical Engineering Iranch, DSS "E-SU: NARY OF T0f 2 CAL REPORT:
This topical report provides a description and verification of certain ccnputer codes used by W_ for structural analysis ond design of primary
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structures and components. The objective of this report is to satisfy p!.i=
the requirements of SRP Sect'on 3.9.1 concern'n; documentation and Wi..
verification of computer programs used for analysis and design of mechanical
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systems and enmponents. The codes described in this report are listed bel ow.
Since some are used sequentially, they are grouped together 53.5 "WE as follows:
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I.
WESTDYN 7, FIXFI13. WESTDYN2
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II.
HECAil m!!!!
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STRUDL, THESSE
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SAND, SPECTA,110DAL sci r=
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DARI-WOSTAS m:.t E:?
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VI.
STHRUST s
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Following is a sumary description of these codes:
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WESTDYN 7 m.:
Performs linear elastic analysis of three-dimensional piping
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M systems subjected to thermal, static and dynamic loads. Dynamic E
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h-analysis is perfomed on lumped ess systems by modal superposition using response spectrum analysis. The resultant internal forces
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and moments are calculated from the. square. root of_ tha sum of the 7
squares of the modal forces and moments.
It hes options which pemit calcuiation of fatigue usage factors in accordance with the A'iSI B31.7 and AS'iE Section III requirements, and the stresses within the piping system in accordance with USAS B31.1, ANSI m.
B31.7 and ASf1E Section III. This progr m was verified by comparing g.
the results of a number of problems solved by other neans with the program generated solutions. These results compared favorably.
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B.
FIXF!1 3
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This program is used to perform transient analysis of a structure
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where the loading history is known, by integrating numerically (by ' predictor / corrector integration technique) the modal equations of motion.
It is used in conjunction with WESTDYN 7 from which it obtains the natural modes and frequencies.
It also permits the
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solution by modal superposition of a class of problems with N
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by considering the impact as external forces.
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WESTDYN 2 EE.
This program accepts the resulting displa.:ement histories from
[F FIXF113 and calculates the internal force and stress histories, h-generating similar results to WESTDYN 7.
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The combination WESTf YN 7/FIXFt13/WESTDYN 2 was checked out by comparing the numeri:a1 and analytical solutions of a canti-levered beam with three masses,- subjected to certain forcing.
functions. These results also compared favorably.
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WECAN This is a large, general-purpose digital computer program for static and dynamic structural analysis by the finite element It approach as well as for themal and flow network analysis.
.r E.?w is intended primarily for elastic and plastic analysis of large 4
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structures consisting of rods, beams, plates, and shells with several hundred degrees of freedom.
It can be applied to problems invol.ing linear and non-linear structural problems.
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(Nonlinearity refers to material properties and. gaps.) This
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section was removed from this report and reissued separately as WCAP 8929. This program has therefore,'not been reviewed herein, but will be evaluated separately.
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III.
ICES STRUDL-II, THESSE p:e STRUDL is a structural program originated at ti.I.T. which is used A.
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to perform static linear elastic frame analysis of reactor coolant 32.
loop equipment support stret"*es. Verification for it is clain,ed thru the fact that it has been in the public domain for many 5
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years and therefore no further verification is
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B.
THESSE is used to evaluate the stresses in the members of reactor system equipment support structures.
It accepts the stiffness calculated from a structural analysis, lands due to deadweight,
4 thermal, pressure _and seismic loads, and loads due to a loss-of-coolant accident from a reactor coolant system analysis. These loads are used individually to obtain the end force and moments components for each member. These components are then combined by a method which differs from any shown in NUREG-0484, Rev.1 " Methodology for Combining Dynamic Responses". However, Westinghouse has committed to provide the actual load combination method for each plant analysis in the applicants' Final Safety Analysis Report.
The combined force components are used to evaluate buckling and yield interaction ratios, and shear ratios under faulted conditions. These ratios are obtained from equations taken from the AISC Maraal of Con-struction,1970 version, which are based on elastic-perfectly plastic behavior. Similar ratios are also evaluated for normal, upset and emergency conditions.
In addition, the resultant stresses due to these force components are also compared to the1 allowable values given in the Final Safety Analysis Report, which the applicant is committed to satisfy and which are based on the loading combinatiers and structural acceptance
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criteria as listed in SRP 3.9.3. -THESSE was verified by applica- -
tion to a three-legged frame support structure, and comparing with hand solutions which shows that the equations are correctly
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IV.
SAND, SpECTA_t MODAL A.
SAND perfoms static, dynamic and thermal stress analysis of linear elastic frame structures.
It is applied to the following five ty' pes of structures:
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Three-dimensional structure-pinned joints.
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TFree-dimensional structure-rigid joints with equal member cross-section moment of inertie.
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Planar structural-rigid joints loaded in a plane.
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4.
Planar structure-rigid joints loaded in a plane.
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Three-dimensional structure-rigid joints doubly r;mmetric gs cross-sections.
K The dynamic analysis yields frequencies and mode shapes, which are
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then used with SPECTA and MODAL for obtaining the responses of M..
.~5i the analyzed structures.
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SPECTA admits the modes and frequencies from SAND and perfroms a response spectrum analysis of SAND-type structures subjected h
1 to seismic excitation.
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MODAL also admits the modes and frequencies from SAID, but performs 1
- T a time history analysis for obtaining the seismic response of the
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SAND-type structures.
It can also be used for obtaining response ee e e.
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spectra within the structures.
These three programs were verified by comparison with hand solutions and solutions which have appeared in the open literature.
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V.
DARI-WOSTAS This is a special purpose finite element program for the dynamic
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analysis of reactor internal structures subjected to time-varying hydraulic loads which occur during blowdown, from reactor coolant gm.
1 flow, and resulting impact froces.
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For analysis the reactor structural system is divided into a number f
of masses connected together by elastic and rigid members which
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p e:r are postulated to experience small vertical, or transverse and m..
rotational, motion.
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The program is a combination of two separate structural progrens 3
designed to solve specific problems:
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WOSTAS for vertical vibration of the reactor internals. Each i=]b Jg;.
mass possesses one vertical displacement degree of freedom.
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DARI for transverse
- vibration of the reactor internals. Each
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GL mass possesses one horizontal displacement and one-inplane g
rotational Jegree of freedom.
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To utilize DARI-WOSTAS the reactor internal structurst system g-
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is idealized by two models:
(1) a transverse model comprised of masses connected by elastic vertical beam and pinjoint
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- Transverse means a vertical structure with horizontal displace-ments.
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,7, elements, and horizontal rigid members and spring and dampers and,(2) a vertical model consisting of masses connected by vertical spring, darg:7 and friction elements.
Both models are g
also capable of treating impact due to gaps between nodes.
The equations of motion are solved by step-by-step integration using Harning's codified predicto -corrector method, developed by IBit.
.:a This program was verified by comparing the results of a number of problems with those obtained from the program WESTDYN. The comparisons show very close agreement of the calculations.
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VI.
STHRUST g..
This program is used for calculating time-history blowdown forcing 12
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functions, which are used as input to programs for structural analysis of pressurized water reactor coolant loops. It is used in conjunction with the hydrodynamic program SATAN. This program its
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provides the transient pressure, mass flow rates, and other
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thermo#vnamic properties as a function of titA.
STHRUST then
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.E calculates the transient hydraulic forces at various locations
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in the coolant loop, such as elbows, pumps and steam generator
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The equation fer calculating the resultant forces is based on the one-dimensional equation for conservation of linear nomentum from
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fluid dynamics.
The loop and its components is represented by e.4 e
8-one-dimensional control volumes on which act the fluid pressure and forces due to gravity and friction. The actual equations used for calculating the forces do nct include inertia nor friction terms. Neglecting the frictional tems is conservative; exclusion of the inertia terms is conservative only if the fluid parameters (mass flow) change relatively slowly with time, and the length i
of the control volumes is short.
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E Verification for this program was claimed by comparing hand and j,
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computer calculations for the sane sample data obtained from SATAN c
SUIMARY OF REGULATORY EVALUATION The topical report was evaluated in accordance with the requirements
!!.T stipulated in the Standard Review Plan, Rev.1, Section 3.9.1, by a detailed review of the theoretical bases and the verification problems
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for the computer codes considered as proprietary. The problems consisted of a comparison of computer generated solutions with
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hand calculated selutions, or solutions obtained from other sources.
Confimatory calculations were also perfomed to verify the methodology M
54 used in the code FIXFli 3 for solving non-linear problems involving jjp
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gaps in structural systems. This work was perfomed by the Brookhaven National Laboratory and is summarized in a note submitted to the NRC
-p titled " Hon-linear Dynamic Analysis of Piping Systems Using the i"
Pseudo force Method." These calculations confimed the adequacy of -
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this methodology.
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-g-Westinghouse has also committed to provide the actual method of internal load combination due to static and dynamic loads, in the applicant's Final Safety Analysis Report. The method described in the FSAR should correspond to one of those described in NUREG-0484, Rev.1, " Methodology for Combining Dynamic Responses!
REGULATORY POSITION We find this report acceptable as a reference to support the applicants conclusions when referenced in utility applications, and an acceptable basis for fulfilling the requirements of 10 CFR 50, Appendix B.
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